Zirconium alloy was chosen for use in the core of water-cooled nuclear reactors because of its low thermal neutron capture cross-section, reasonable mechanical properties and adequate corrosion resistance in high temperature water. 锆合金因为具有良好的抗高温水及过热蒸汽的腐蚀性能、良好的力学强度和塑性以及较低的热中子吸收截面,在反应堆内得以广泛应用。